| Impurity driven corrosion behavior of HAYNES® 230® alloy in molten chloride Salt B D’Souza, W Zhuo, Q Yang, A Leong, J Zhang Corrosion Science 187, 109483, 2021 | 31 | 2021 |
| Europium induced alloy corrosion and cracking in molten chloride media for nuclear applications S Guo, W Zhuo, Y Wang, J Zhang Corrosion Science 163, 108279, 2020 | 28 | 2020 |
| Electrochemical extraction of lanthanum in molten fluoride salts assisted by KF or NaF Y Wang, J Ge, W Zhuo, S Guo, J Zhang Electrochemistry Communications 104, 106468, 2019 | 18 | 2019 |
| Selective electrodeposition of europium and samarium in molten LiCl-KCl with copper and aluminum electrodes J Ge, Q Yang, Y Wang, W Zhuo, M Du, J Zhang Journal of The Electrochemical Society 167 (2), 022501, 2020 | 17 | 2020 |
| Electrochemical separation study of LaF3 in molten FLiNaK salt Y Wang, J Ge, W Zhuo, S Guo, J Zhang Journal of Nuclear Materials 518, 162-165, 2019 | 16 | 2019 |
| XRD and SEM/EDS characterization of two quaternary fuel alloys (U-2.5 Mo-2.5 Ti-5.0 Zr and U-1.5 Mo-1.5 Ti-7.0 Zr in wt.%) for fast reactors W Zhuo, Y Xie, MT Benson, J Ge, RD Mariani, J Zhang Materials Characterization 170, 110696, 2020 | 15 | 2020 |
| Effect of neighboring wall on the fluid added mass of CAP1400 spent fuel storage rack Y Liu, D Lu, W Li, W Zhuo Progress in Nuclear Energy 101, 177-187, 2017 | 12 | 2017 |
| The studies of mixing and thermal stratification in SMR containments F Niu, W Zhuo, J Cai, X Su, Y Hu, Y Zhao, T Ma, Y Wang, Y Yu Nuclear Engineering and Design 298, 14-24, 2016 | 12 | 2016 |
| Experimental and CFD analysis of the effects of debris deposition across the fuel assemblies MS Azam, F Niu, D Wang, W Zhuo Nuclear Engineering and Design 332, 238-251, 2018 | 11 | 2018 |
| Hermeticity and tensile experiment of small plate-type SiC ceramic composites for advanced reactor applications W Zhuo, F Niu, Y Zhao, J Liu Annals of Nuclear Energy 110, 1098-1106, 2017 | 9 | 2017 |
| Experimental investigation of FCCI using diffusion couple test between UZr fuel with Sb additive and cladding W Zhuo, Y Xie, MT Benson, Q Yang, RD Mariani, J Zhang Nuclear Science and Engineering 194 (6), 462-476, 2020 | 8 | 2020 |
| Experimental analysis of steam mixing and thermal stratification phenomena related to small steel containment studies S Wang, Y Wang, W Zhuo, F Niu, Y Yu, Z Guo, Y Shen, W Chen, X Jiang Annals of Nuclear Energy 109, 103-112, 2017 | 7 | 2017 |
| Influence of injection temperature and flow rate on mixing and stratification in small passively cooling enclosures WQ Zhuo, FL Niu, JC Cai, XW Su, YQ Hu, YG Zhao, Y Yu Nuclear Science and Techniques 27, 1-11, 2016 | 6 | 2016 |
| Experimental assessment of antimony (Sb) in pure uranium for immobilizing fission product lanthanides W Zhuo, Y Xie, MT Benson, H Wu, RD Mariani, J Zhang Journal of Nuclear Materials 534, 152135, 2020 | 5 | 2020 |
| Modeling and experimental studies on air buoyant jets for application to small containments T Ma, F Niu, W Zhuo, Y Wang, T Warraich, S Azam Annals of Nuclear Energy 109, 212-219, 2017 | 5 | 2017 |
| Aluminum alloy corrosion and precipitation in high-temperature flow loop simulating environment after loss-of-coolant accidents D Wang, A Leong, W Zhuo, H Wu, Q Yang, J Zhang Journal of Alloys and Compounds 896, 163035, 2022 | 4 | 2022 |
| Thermophysical and thermodynamic properties of NaF-BeF2-UF4-ZrF4 fuel salt J Park, W Zhuo, C Ridder, A Leong, J Zhang Materials Today Communications 37, 107211, 2023 | 3 | 2023 |
| The formation mechanism of the Zr rind in U-Zr fuels MT Benson, T Yao, JN Zelina, F Teng, D Murray, F Di Lemma, ... Journal of Nuclear Materials 572, 154057, 2022 | 3 | 2022 |
| Solid-state phase transitions of two quaternary metallic fuel alloys (U-2.5 Mo-2.5 Ti-5.0 Zr and U-1.5 Mo-1.5 Ti-7.0 Zr in wt.%) W Zhuo, H Wu, Y Xie, MT Benson, J Zhang Journal of Nuclear Materials 555, 153134, 2021 | 3 | 2021 |
| Assessment of head loss through LOCA-generated debris deposited in PWR fuel assemblies D Wang, F Niu, R Liang, W Zhuo, S Wang Annals of Nuclear Energy 137, 107037, 2020 | 2 | 2020 |
